Experimental analysis of the power curve sensitivity test series at ROSA-III-Reference-Cited by-同舟云学术

Experimental analysis of the power curve sensitivity test series at ROSA-III

Published:1985-05 Issue:2 Volume:86 Page:267-287
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Koizumi Y.,Iriko M.,Yonomoto T.,Tasaka K.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference19 articles.

1. ROSA-III program at JAERI for BWR LOCA/ECCS integral tests;Tasaka,1980

2. ROSA-III system description for fuel assembly No. 4;Anoda,1981

3. BWR blowdown/emergency core cooling program 64-rod bundle core spray interaction (BD/ECC 1A);Lee,1981

4. BWR blowdown/emergency core cooling program 64-rod bundle core spray interaction (BD/ECC 1A);Hwang,1981

5. BWR loss of coolant integral test: parallel channel effect;Murase;NUREG/CP-0027,1983

Cited by 6 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. BWR Loss-of-Coolant Accident Tests at ROSA-III with High Temperature Emergency Core Coolant Injection;Journal of Nuclear Science and Technology;1988-02

2. Core heat transfer analysis during a BWR LOCA simulation experiment at ROSA-III;Nuclear Engineering and Design;1987-08

3. EFFECT OF HEAT-GENERATION DIFFERENCE AMONG FUEL BUNDLES ON CORE THERMAL-HYDRAULICS DURING 200-PERCENT AND 5-PERCENT LOSS-OF-COOLANT ACCIDENT EXPERIMENTS AT ROSA-III;J NUCL SCI TECHNOL;1987

4. Effect of Heat Generation Difference among Fuel Bundles on Core Thermal-Hydraulics during 200% and 5% Loss-of-Coolant Accident Experiments at ROSA-III;Journal of Nuclear Science and Technology;1987-01

5. INVESTIGATION OF BREAK LOCATION EFFECTS ON THERMAL-HYDRAULICS DURING INTERMEDIATE BREAK LOSS-OF-COOLANT ACCIDENT EXPERIMENTS AT ROSA-III;J NUCL SCI TECHNOL;1986